ML19225C354
| ML19225C354 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/05/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225C355 | List: |
| References | |
| NUDOCS 7907270341 | |
| Download: ML19225C354 (5) | |
Text
UNITED STATES yV
-t NUCLEAR REGULATORY COMMISslON j, l*i j
W ASHINGTON. D. C. 20555 a.
E
\\'...../
GEORGIA POWER COMPANY OGLETHORPE ELECTRIC MEMBERSHIP CORPORATION MUNICIPAL ELECTRIC ASSOCIATION OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N9. 50-366 EDWIN I. HATCH NUCLEAR PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License Nol NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
ihe application for amendment by Georgia Power Company, et al.
(the licensee) dated July 2,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by 1.his amendment can be conducted without endangering the health and safety of tM public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission's regulations and all applicable requirements i
have been satisfied.
i 427 003 7 907270 3 9 /
/c 2.
Acc6rdingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 9, are hereby incor-porated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
(
,ppolito, Chief T omas Operating Reactors Branch #3 Division of Operating P.eactors i
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 5,1979 I.
I I
l 427 00//
ATTACHMENT TO LICEN.'E AMEi1DMENT NO. 9 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following nages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating th' area of change.
Remove Insert 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 1
427 ogy
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATTON 5
VALVE GROUPS ff!NIMUM NUMBER APPLICABLE M
OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION
_ ; ION Si 4.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION Z
1 a.
IIPCI Steam Line Flow -liigh##
3 1
1,2,3 26 l
m (2E41-N004 and 2E41-N005) b.
HPCI Steam Supply Pressure -
Low (2E41-N001 A, B, C, D) 3, 8 2
1,2,3 26 y
c.
HPCI Turbine Exh;ust Diaphragm o
Pressure - thgh (2E41-N012 A,B,C,0) 3 2
1,2,3 26 OM d.
IIPCI Equipment Room Temperature - High (2E41-N610 A, B) 3 1
1,2,3 26 5
e.
Suppression Pool Area Ambient Temperature-High (2E51-N603 C, D) 3 1
1,2,3 26 m'
f.
Suppression Pool Area A Temp.-High (2E51-N604 C, D)
, 'l 1
1,2,3 26 9
Suppres'sion Pool Area Temperature g)
Timer Relays (2E41-M603 A, B) 3 1
1, 7, 3 26 N
g h.
Emergency Area Cooler Temperature-g Hir;h (2E41-N602 A, B) 3 1
1,2,3 26 i.
Drywell Pressure-High
!?
(2 Ell-N0ll C, D) 8 1
1,2,3 26 j.
Logic Power l'onitor (2E41-Kl)
NA(h) 1 1,2,3 27
- e hot required OPERABLE during performance of the special startup test program on HPCI and RCIC reliability authorized by Amendment No. 9
TABLE 3.3.2-1 (Continued) i IS01.ATION ACTUATION INSTRUMENIATION I
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL yi SIGNAL (a)
PER. TRIP SYSTEM (b)(c)
CONDITION ACTION TRIP FUNCTION a
2 5.
REACTOR CORE ISOLATION i
COOLING SYSTEM ISOLATION c5 a.
RCIC Steam Line Flow-High##
4 1
1, 2, 3 26 l
RCIC Steam Supply Pressure -
Low (2E51-N019 A, B, C, D) 4, 9 2
1,2,3 26 c.
RCIC Turbine Exhaust Diaphragm Pressure - liigh 4
2 1, 2, 3 26 (2E51-N012 A, B, C, D) d.
Emergency Area Coo'er Temperature -
High (2E51-N602 A, B) 4 1
1,2,3 26 Suppression Pool Area Ambient 4
1 1,2,3 26 e.
{
iTemperature-High i
(2E51-H603 A, B) k f.
Suppression Pool Area a T-High
'4 1
1,2,3 26 m
(2E51-N604 A. B) b g.
Suppression Paol Area Temperature 4{3) 1 1,2,3 26 Timer Relays (2E51-M602 A, B)
N h.
Drywell Pressure - High 9
1 1,2,3 26
[o (2Cll-N0ll A, B)
NA(h) 1 1,2,3 27 O
i.
Logic Power Monitor (2E51-Kl) g N
6.
SHUTOOWN COOLING SYSTEM ISOLATION Reactor Vessel Water Level-Low 2, 5, 6, 10, 11, 2
3, 4, 5 26 a.
(2B21-N017 A, B, C, D) 12 b.
Reactor Steam Dome Pressure-High 11 1
1,2,3 28 (2831-N018 A, B)